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Measurement of the neutron capture cross-section of ~(238)U using the neutron activation technique

机译:用中子活化技术测量〜(238)U的中子俘获截面

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摘要

The ~(238)U(n, c) ~(239)U reaction cross-section at average neutron energy of 3.7 ± 0.3 MeV from the ~7Li(p, n) ~7Be reaction has been determined using activation and off-line c-ray spectrometric technique. The ~(238)U(n, c) ~(239)U and ~(238)U(n, 2n) ~(237)U reaction cross-sections at average neutron energy of 9.85 ± 0.38 MeV from the same ~7Li(p, n) ~7Be reaction have been also determined using the above technique. The experimentally determined ~(238)U(n, c) ~(239)U and ~(238)U(n, 2n) ~(237)U reaction cross-sections were compared with the evaluated data of ENDF/B-VII, JENDL-4.0, JEFF-3.1 and CENDL-3.1. The experimental values were found to be in general agreement with the evaluated value based on ENDF/B-VII, and JENDL-4.0 but not with the JEFF-3.1 and CENDL-3.1. The present data along with literature data in a wide range of neutron energies were interpreted in terms of competition between different reaction channels including fission. The ~(238)U(n, c) ~(239)U and ~(238)U(n, 2n) ~(237)U reaction cross-sections were also calculated theoretically using the TALYS 1.2 computer code and were also found to be in agreement experimental data.
机译:使用激活和离线方法确定了〜7Li(p,n)〜7Be反应的中子平均能量为3.7±0.3 MeV时的〜(238)U(n,c)〜(239)U反应截面c射线光谱技术。在相同的〜7Li下,平均中子能量为9.85±0.38 MeV时〜(238)U(n,c)〜(239)U和〜(238)U(n,2n)〜(237)U反应截面(p,n)〜7Be反应也已使用上述技术确定。将实验确定的〜(238)U(n,c)〜(239)U和〜(238)U(n,2n)〜(237)U反应截面与ENDF / B-VII的评估数据进行比较,JENDL-4.0,JEFF-3.1和CENDL-3.1。实验值与基于ENDF / B-VII和JENDL-4.0的评估值基本一致,但与JEFF-3.1和CENDL-3.1不一致。根据包括裂变在内的不同反应通道之间的竞争解释了当前数据以及有关广泛中子能量的文献数据。理论上也使用TALYS 1.2计算机代码计算了〜(238)U(n,c)〜(239)U和〜(238)U(n,2n)〜(237)U反应截面,并且还发现了同意实验数据。

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